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Overview of coordinated spherical tokamak research in Japan

Y. Takase, A. Ejiri, T. Fujita, K. Hanada, H. Idei, M. Nagata, T. Onchi, Y. Ono, H. Tanaka, N. Tsujii2022年被引用 5Nuclear FusionIF 3出版社

Spherical tokamak (ST) research in Japan has produced many innovative results: (i) plasma start-up to Ip > 70 kA was achieved by electron cyclotron wave (ECW) with N∥ = 0.75, while electron heating to Te > 500 eV was achieved with N∥ = 0.26 on QUEST. (ii) The radiofrequency (RF)-induced transport model was combined with the x-ray emission model, and extended magnetohydrodynamics equilibrium with kinetic electrons was developed to interpret fast-electron-dominated lower hybrid wave sustained plasmas on TST-2. (iii) Density as high as 30 times the cutoff density was achieved by electron Berstein wave current drive combined with electron beam injection on LATE. (iv) Multiple plasmoids formed by tearing instability in the elongated current sheet were observed, and flux closure and ion heating by plasmoid-mediated fast magnetic reconnection were observed on HIST. (v) Optimization of ECW-assisted inductive start-up with a vertical field with positive decay index was performed on TST-2. (vi) Stabilization of the vertical displacement event by a set of upper and lower helical field coils was demonstrated on TOKASTAR-2. (vii) A 6 h discharge was achieved by cool-down of the center stack cover on QUEST, where the plasma duration limit was consistent with the wall saturation time estimated by modeling. (viii) Extension of ion heating by plasma merging was achieved on TS-3U, TS-4U, UTST, MAST, and ST40.

日本語訳

日本における球状トカマク(ST)研究は多くの革新的成果を生み出してきた:(i) QUESTにおいて、N∥ = 0.75の電子サイクロトロン波(ECW)によりIp > 70 kAへのプラズマ立ち上げが達成され、一方N∥ = 0.26によりTe > 500 eVへの電子加熱が達成された。(ii) 高周波(RF)誘起輸送モデルをX線放射モデルと組み合わせ、運動論的電子を考慮した拡張電磁流体力学平衡を開発し、TST-2における高速電子支配の低域混成波維持プラズマを解釈した。(iii) LATEにおいて、電子バーンスタイン波電流駆動と電子ビーム入射を組み合わせることにより、遮断密度の30倍もの高密度が達成された。(iv) HISTにおいて、細長い電流シート内のテアリング不安定性によって形成される複数のプラズモイドが観測され、プラズモイド媒介の高速磁気リコネクションによる磁束閉合とイオン加熱が観測された。(v) TST-2において、正の減衰指数を持つ鉛直磁場を用いたECW支援誘導立ち上げの最適化が実施された。(vi) TOKASTAR-2において、上部および下部のヘリカル磁場コイルの組による垂直変位事象の安定化が実証された。(vii) QUESTにおいて、センタースタックカバーの冷却により6時間放電が達成され、プラズマ持続時間の限界はモデリングにより推定された壁飽和時間と一致した。(viii) TS-3U、TS-4U、UTST、MAST、およびST40において、プラズマ合体によるイオン加熱の拡張が達成された。

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